RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 13.0, Conduct of Operations Tables
| ML11202A193 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/29/2011 |
| From: | Exelon Generation Co, Exelon Nuclear |
| To: | NRC/FSME |
| References | |
| RS-11-100 | |
| Download: ML11202A193 (33) | |
Text
DRESDEN - UFSAR Rev. 7 June 2007 13.1-1 13.0 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE 13.1.1 Corporate Management and Technical Support Organization
EGC's corporate organization and its functions and responsibilities are described in Section 1.0 of Quality Assurance Program Topical Report NO-AA-10
[1] as revised and filed with the NRC. Organizational charts within this report reflect the current corporate structure and the departments which provide technical support for operation and backup support. Where appropriate, these services are provided by outside groups through contractual agreements.
13.1.2 Plant Operating Organization The overall organization of Dresden Station is in accordance with Chapter 1 of Quality Assurance Program Topical Report NO-AA-10
[1] which describes the line of responsibility from the Chairman and Chief Executive Officer down through the station staff.
13.1.3 Plant Personnel Responsibility and Authority
The basic job functions of Plant positions are described in QA Topical Report NO-AA-10
[1] and Station Administrative Procedures.
13.1.4 Deleted
13.1.5 Deleted 13.1.6 Deleted
13.1.7 Operating Shift Crews Minimum shift manning requirements are listed in Technical Specification Section 5.2 and in the E-Plan.
DRESDEN - UFSAR Rev. 6 June 2005 13.1-2 13.1.8 Qualifications of Nuclear Plant Personnel The station positions requiring possession of an SRO License are described in Section 5 of the Technical Specifications.
Qualifications of the station management and operating staff meet minimum acceptable levels as described in ANSI N18.1-1971, with exceptions and clarifications as noted in Section 5 of the Technical Specifications.
13.1.9 References
- 1. Quality Assurance Program Topical Report NO-AA-10, "Quality Assurance Program for Nuclear Generating Stations," (current revision).
DRESDEN - UFSAR Rev. 6 June 2005 13.2-1 13.2 TRAINING 13.2.1 Plant Training Programs Dresden Nuclear Station provides training formulated to develop and maintain an organization qualified to operate, maintain, and support the facility in a safe and reliable manner. Achievement of this goal is based on a philosophy of providing training developed from a systems approach to training (SAT). This philosophy is consistent with both Nuclear Regulatory Commission (NRC) requirements 10 CFR parts 50 and 55, as well as the Institute of Nuclear Power Operations (INPO) recommendations for the accreditation of training programs by the National Academy of Nuclear Training. Program descriptions are contained in sections 13.2.1.1 and 13.2.1.2.
Retraining and replacement training of station personnel is conducted in accordance with Technical Specification Section 5.3 Unit Staff Qualifications. The frequency of retraining and continuing training programs are determined by following the SAT-based training process.
13.2.1.1 Training Programs for Licensed Personnel
13.2.1.1.1 Replacement License Training Replacement license training will provide SAT-based training to reactor operator (RO) and senior reactor operator (SRO) candidates in accordance with 10 CFR 55. Replacement license training will
comply with SAT-based training requirements by maintaining accreditation.
13.2.1.1.2 License Operator Requalification Training License operator requalification training will provide SAT-based training to ROs and SROs in accordance with 10 CFR 55. License operator requalification training will comply with SAT-based training requirements by maintaining accreditation.
13.2.1.1.3 Simulator Training ROs and SROs may perform control manipulations on the simulator required as part of the training in section 13.2.1.1.1 and 13.2.1.1.2. Training will maintain a certified simulator in accordance with the provisions in 10 CFR 55.
DRESDEN - UFSAR Rev. 5 January 2003 13.2-2 13.2.1.1.4 Training of Licensed Supervisor The shift supervisor training program will comply with the SAT-based training requirements and consists of training in those administrative duty areas above and beyond licensed duties.
13.2.1.1.5 Training for Shift Technical Advisors Shift Technical Advisors not meeting the dual-role SRO/STA requirements as described in section 13.2.1.1, will be trained and qualified in accordance with Option 2 of the Commission Policy Statement on Engineering Expertise (50 FR 43621 October 28, 1985). Shift technical advisor training will comply with the SAT-based training requirements.
13.2.1.2 Training Programs for Nonlicensed Personnel
13.2.1.2.1 Training for Mechanical Maintenance Personnel Mechanical maintenance training will provide SAT-based training to mechanical maintenance personnel in accordance with 10 CFR 50.120. Mechanical maintenance training will comply with the SAT-based training requirements by maintaining accreditation.
13.2.1.2.2 Training for Electrical Maintenance Personnel
Electrical maintenance training will provide SAT-based training to electrical maintenance personnel in accordance with 10 CFR 50.120. Electrical maintenance training will comply with the SAT-based training requirements by maintaining accreditation.
13.2.1.2.3 Training for Instrument Maintenance Personnel Instrument maintenance training will provide SAT-based training to instrument maintenance personnel in accordance with 10 CFR 50.120. Instrument maintenance training will comply with the SAT-based training requirements by maintaining accreditation.
13.2.1.2.4 Training for Radiation Protection Personnel
Radiation protection training will provide SAT-based training to radiation protection personnel in accordance with 10 CFR 50.120. Radiation protection training will comply with the SAT-based training requirements by maintaining accreditation.
DRESDEN - UFSAR Rev. 5 January 2003 13.2-3 13.2.1.2.5 Training for Chemistry Personnel Chemistry training will provide SAT-based training to chemistry personnel in accordance with 10 CFR 50.120. Chemistry training will comply with the SAT-based training requirements by maintaining accreditation.
13.2.1.2.6 Training for Non-licensed Operators Non-licensed operator training will provide SAT-based training to non-licensed operator personnel in accordance with 10 CFR 50.120. Non-licensed operator training will comply with the SAT-based training requirements by maintaining accreditation.
13.2.1.2.7 Training for Engineering Support Personnel Engineering support training will provide SAT-based training to engineering support staff in accordance with 10 CFR 50.120. Engineering support training will comply with the SAT-based training requirements by maintaining accreditation.
13.2.1.2.8 Training for Fuel Handlers Fuel Handler Training ensures that Fuel Handlers are adequately trained in the area of systems, components, and task performances required to fulfill the duties and responsibilities of that position. Fuel handler training will provide SAT-based training to fuel handler personnel.
13.2.1.2.9 Training for Emergency Preparedness Personnel Emergency Preparedness (EP) Training is required for all designated response personnel who may be called upon to assist in an emergency. Station personnel who could be affected by an emergency are provided with training on the Emergency Plan (E-Plan) in order to provide for health and safety of the public, including station employees, and to limit damage to the facility and property.
Emergency Preparedness Training typically consist of the following topics:
A. Generic E-Plan training B. Site-specific E-Plan training C. Emergency Plan Implementing Procedures D. Operating Experiences DRESDEN - UFSAR Rev. 3 13.2-4 13.2.1.3 Nuclear General Employee Training 13.2.1.3.1 All employees (and others) who require unescorted access to the Protected Area of the station will receive training in the following areas:
- a. General description of plant and facilities b. Emergency Plan procedures c. Fire Protection Program and Procedures d. Security Requirements and Practices e. Safety Program f. Quality Assurance Program g. Radiological Protection Program 13.2.1.3.2 All employees (and others) who have unescorted access to Radiation Controlled Areas of the station will receive in-depth instruction in all aspects of radiation protection and, as required, respiratory protection. Subject material will include but will not be limited to the following:
- a. Handling radioactive material b. Controls and access requirements c. Biological effects of ionizing radiation 13.2.1.3.3 Some employees receive, as part of their specialty training a general plant information course. This course consist of overall plant description, thermodynamic fundamentals, nuclear physics fundamentals, and plant systems fundamentals.
13.2.1.3.4 Review of appropriate department and station procedures are specified in department specialty training programs.
13.2.1.4 Fire Brigade Training A training program for the fire brigade is maintained under the direction of Operating Engineer and meets or exceeds the requirements of Section 27 of the National Fire Protection Association (NFPA) Code - 1975, except for the fire brigade training sessions which are held at least quarterly.
13.2.2 Replacement and Retraining 13.2.2.1 Licensed Operators - Requalification Training NOTE: All replacement and retraining are embedded within the accredited programs as described in sections 13.2.1.1 and 13.2.1.2.
DRESDEN - UFSAR Rev. 3 13.2-5 13.2.3 Applicable NRC Documents The following is a list of documents referenced in preparation of the Dresden training programs:
- a. 10 CFR 50 b. 10 CFR 55 c. 10 CFR 19 d. Generic Letter 87-07 e. Regulatory Guide 1.120 f. Regulatory Guide 1.8 g. Regulatory Guide 8.2 h. Regulatory Guide 8.8 i. Regulatory Guide 8.10 j. Regulatory Guide 8.13 k. NUREG - 0737 l. 50 FR 43621, Option 2
DRESDEN - UFSAR (Sheet 1 of 1)
Table 13.2-1 UNIT 2 PERSONNEL TRAINING Dresden Title Activity F BWRTED OP ST OJ OS X X X Plant Supt. X X X X X X Ass't. Supt. X X X X X X Op. Engr. X X X X X X Shift Engr. & Train. Supv. X X X X X X X Startup & Shift Foreman X X X X X X X NSO X X X X X X Equip. Oper. X X X X X X Equip Att. X X X X X Supv. Engr. X X X X Thermal Engr. X X X X Instr. Engr. X X X X Rad. Chem. Engr. X X X X
Maint. Engr. & Master Mech. X X X X Maint. Foreman X X X X Fuel Forman X X X X X Other plant personnel X X X X F - Fundamental Courses BWRT - Boiling Water Reactor ED - Equipment Description Course Technology Course ST - Simulator Training OP - Operating Procedure Course OS - On Site Training OJ - On the Job BWR Training DRESDEN - UFSAR Rev. 5 January 2003 13.3-1 13.3 EMERGENCY PLANNING An Emergency Plan (E-Plan) has been developed which considers the consequences of radiological and non-radiological emergencies. The E-Plan provides for the protection of the health and safety of the public, including EGC employees, the limitation of damage to facilities and property, and the restoration of affected facilities in the event of an emergency. The E-Plan includes a site specific annex which contains additional information and guidance specific to each nuclear station.
The E-Plan describes the emergency organization, including assignments of authority and responsibility. The E-Plan provides for detection and evaluation of emergency situations and discusses protective measures, communications, coordination and notification of governmental authorities, document review and control, emergency preparedness assessment, and training of the participating personnel. Drills and Exercises to ensure readiness on the part of plant personnel are defined and described within the E-Plan.
13.3.1 References
- 1. Exelon Nuclear Radiological Emergency Plan (current revision).
- 2. Exelon Nuclear Radiological Emergency Plan Annex, Dresden Station (current revision).
DRESDEN - UFSAR Rev. 4 13.4-1 13.4 REVIEW AND AUDIT Review and Investigative Functions (committees) are established in accordance with the Quality Assurance Program. These functions include the Independent Technical Review, Plant Operations Review Committee, and the Nuclear Safety Review Board. Station Audits are performed as specified in the Quality Assurance Program described in Chapter 17.
In the event that a safety limit is exceeded, the reactor is shut down in accordance with the Technical Specifications and the conditions of shutdown are promptly reported to the Dresden Station Site Vice President or his designated alternate. Reactor operation is not resumed until authorized by the NRC. The incident receives onsite and offsite investigations and reviews pursuant to the Technical Specifications. For each occurrence, a separate report is submitted to the NRC as required by Technical Specifications and 10 CFR 50.73.
Any reportable occurrence is promptly reported to the Site Vice President or his designated alternate. Personnel performing the onsite review and investigative function will review investigation results and prepare a report covering the evaluation and recommendations to prevent recurrence. A separate report for each reportable occurrence is submitted to the NRC as required by Technical Specifications and 10 CFR 50.73.
13.4.1 Plant Operations Review Committee Personnel participating on the Plant Operations Review Committee are responsible for reviewing a variety of activities and documents as specified in the Quality Assurance Program. In accordance with Quality Assurance Program, certain of these reviews are reviewed by the Nuclear Safety Review Board.
13.4.2 Nuclear Safety Review Board Personnel participating on the Nuclear Safety Review Board are responsible for reviewing a variety of documents as specified in the Quality Assurance Program.
DRESDEN - UFSAR Rev. 4 13.6-1 13.6 SECURITY EGC implements and maintains in effect all provisions of the NRC-approved physical security, guard training and qualification, and safeguards contingency plans for Dresden Station in accordance with the operating licenses. The plans are specified in the following documents, as revised and filed with the NRC:
A. "Dresden Nuclear Power Station Security Plan," B. "Dresden Nuclear Power Station Security Personnel Training and Qualification Plan," and C. "Dresden Nuclear Power Station Safeguards Contingency Plan." These plans meet the requirements of 10 CFR 73.55 and Part 73, Appendices B and C.
The security plan documents contain safeguards information protected under 10 CFR 73.21 and are, therefore, withheld from public disclosure. Some general information relating to security is presented in the following paragraphs.
The Site Vice President has the ultimate responsibility and authority for security at the Station. Below the Vice President, the management of the security organization is independent of the site management. Authority for administration of the security organization is delegated from the Security Director to the Station Security Administrator (see Section 13.1). The Station Security Administrator reports directly to the Security Director and maintains an information and coordinator channel to the Site Vice President.
Station access is controlled by station security in accordance with the Dresden security plan and Dresden administrative procedures.
The following area designations are used at the station:
A. Unrestricted area: that area beyond the site property line.
B. Owner Controlled Area: that area between the station security fence and the property boundary line.
C. Unposted area: that area within the station security fence that is not part of a radiologically posted area.
D. Radiologically posted areas: those areas posted as radiation areas, high radiation areas, radioactive materials areas, airborne radioactivity areas, or combinations thereof. Access to radiologically posted areas for all work is controlled in accordance with station radiation protection procedures.
E. Protected area: that area within the owner-controlled area enclosed by a station security fence in which the main buildings are located. Access to the protected area is controlled.
DRESDEN - UFSAR Rev. 2 13.6-2 F. Vital area: any area within the protected area which contains vital equipment. Vital equipment is any plant equipment, system, or device whose failure or destruction could directly or indirectly endanger public health and safety by a release of radioactivity which could result in a total radiation dose in excess of the limits established by 10 CFR 100.11. Equipment or systems which would be required to function to protect public health and safety following such failure or destruction are also considered vital equipment. Security equipment is not considered vital equipment. All vital equipment is contained in vital areas.
Normal access to the protected area is through the gatehouse. Personnel entering the gatehouse are screened by security systems, e.g., explosive and firearms detectors. When necessary, personnel are given a pat-down search in accordance with the requirements of the Dresden security plan.
Final entry to the protected area is controlled by a computerized card reader in conjuntion with a hand geometry reader system at the Main Access Facility (MAF). Movement within the protected area is controlled by a computerized card reader system.
Security personnel coordinate with Training and Radiation Protection Department personnel to ensure that applicable entry requirements are met.
DRESDEN - UFSAR Rev. 8 June 2009 13.7-1 13.7 RECORDS Quality assurance records are retained to furnish evidence of activities affecting quality. These records are stored from the time of their creation or receipt until their ultimate disposal in a manner which meets the requirements of applicable standards, codes, and regulatory agencies with regard to maintenance, preservation, and protection of files.
Records may be in various forms such as logs, reports, drawings, or meeting minutes.
Records are kept in a manner convenient for review and retained for the period of time specified in Table 13.7-1. It also describes specific records within each type and specifies the minimum required retention period. Record types are briefly discussed in the following subsections.
Other records are retained in accordance with schedules established by NRC orders, Federal Power Commission regulations, and Illinois Commerce Commission regulations. The retention periods for these records are specified in Dresden's Records Retention Schedule.
13.7.1 Control Room Records Operating Logs are reviewed and maintained in accordance with approved administrative programs.
13.7.2 Plant Operation Records
Plant operation records provide pertinent information on the history of unit power production, operational excursions, operational testing, and other quality activities. For example, records of normal plant operation include notation of power levels and periods of operation at each power level.
13.7.3 Procedure Changes
Records of changes to procedures required by the Quality Assurance Topical Report NO-AA-10 as well as other procedures which affect nuclear safety, are retained.
DRESDEN - UFSAR Rev. 2 13.7-2 13.7.4 Review Committee Transactions
Records of review committee transactions include minutes of meetings and results of reviews performed by the Plant Operations Review Committee and Nuclear Safety Review Board.
13.7.5 Radiological and Chemical Records Included in this category of records are the occupational radiation exposure records for all plant personnel, including contractors and plant visitors, in accordance with 10 CFR 20, as well as radiation surveys, offsite environmental monitoring records, and others as noted in Table 13.7-1.
13.7.6 Maintenance Records This category includes records of maintenance and activities (substitution, inspection, and/or repair) for principal equipment pertaining to nuclear safety and the reasons for the maintenance. It also includes records of periodic checks, inspections, calibrations, and/or corrective actions (if any) performed in accordance with Technical Specification surveillance requirements. These records are maintained by the Maintenance Superintendent.
13.7.7 Records of Facility Description and Evaluation
Records of facility description and evaluation include drawings, descriptions of plant changes, evaluations performed in accordance with 10 CFR 50.59, and records of environmental qualification.
13.7.8 Personnel Records Personnel records address the qualification, experience, training, and retraining of individual staff members.
DRESDEN - UFSAR Rev. 6 June 2005 Table 13.7-1 REQUIREMENTS FOR RECORD RETENTION(a) (Sheet 1 of 2)
Record Type Record Description Minimum Retention Period Control room records Shift Engineers' logs 5 years Plant operation records Normal plant operation 5 years Reportable events 5 years Safety limit events 5 years Reactor coolant system inservice inspections Life of plant Transient or operational cycling of life-limited components Life of plant Physics tests and other tests pertaining to nuclear safety 5 years Procedure changes Changes to procedures as required by Quality Assurance Topical Report NO-AA-10 5 years Review committee transactions Reviews by Plant Operations Review Committee Life of plant Reviews by Nuclear Safety Review Board Life of plant Radiological records Personnel exposure records Life of plant Radioactivity in liquid and gaseous wastes released to the environment Life of plant Plant radiation and contamination surveys Life of plant Offsite environmental monitoring surveys Life of plant DRESDEN - UFSAR Rev. 6 June 2005 Table 13.7-1 REQUIREMENTS FOR RECORD RETENTION(a) (Sheet 2 of 2)
Record Type Record Description Minimum Retention Period Radioactive material shipments Life of plant Byproduct material inventory 5 years Source leak test results 5 years New and spent fuel inventory Life of plant New and spent fuel assembly histories Life of plant Maintenance records Substitution or replacement of principal equipment pertaining to nuclear safety Life of plant Maintenance of principal equipment pertaining to nuclear safety 5 years Periodic checks and calibrations to meet Technical Specification surveillance requirements 5 years Records of facility description and evaluation Equipment changes or reviews of tests and experiments to
comply with 10 CFR 50.59 5 years Changes to the plant as it is described in the SAR Life of plant Plant drawings (updated, corrected, and as-built) Life of plant Environmental qualification Life of plant Personnel records Staff member qualifications, experience, training, and retraining Life of plant (a) Changes to this table must be made via the provisions of 10 CFR 50.54(a) until the record retention requirements are listed in the Exelon Nuclear QA Topical Report NO-AA-10.